Title of article
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure
Author/Authors
Pokor، نويسنده , , C and Brechet، نويسنده , , Y and Dubuisson، نويسنده , , P and Massoud، نويسنده , , J.-P and Barbu، نويسنده , , A، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2004
Pages
11
From page
19
To page
29
Abstract
Irradiation damage in three austenitic stainless steels, SA 304L, CW 316 and CW Ti-modified 316, is investigated both experimentally and theoretically. The density and size of Frank loops after irradiation at 320 and 375 °C in experimental EBR II, BOR-60 and OSIRIS reactors for doses up to 40 dpa are characterized by TEM. The evolution of the initial dislocation network under irradiation is evaluated. A cluster dynamics model is proposed to account quantitatively for the experimental findings.
Journal title
Journal of Nuclear Materials
Serial Year
2004
Journal title
Journal of Nuclear Materials
Record number
1358350
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